Published May 21, 1987 | Version v1
Report Restricted

Development of a policy for the use of PRA [Probabilistic Risk Assessment] in the deployment of advanced LWRs and for addressing severe accident considerations

Creators

  • 1. PRD Consulting (USA)

Description

In 1985, the US Department of Energy initiated the Advanced Reactor Severe Accident Program (ARSAP). An overall objective of ARSAP is to resolve severe accident issues as they apply to advanced light water reactor (ALWR) design certification. A portion of ARSAP involves evaluating the use of, and establishing methodology for, the application of Probabilistic Risk Assessment (PRA) to these designs. This paper discusses the results of an effort to identify appropriate applications of PRA to ALWRs including examples

Availability note (English)

Available from NTIS, PC A02/MF A01; 1 as DE88006757.

Files

Restricted

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Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
EGG-M--14387

Conference

Title
international topical meeting on probabilistic safety assessment and risk management.
Acronym
PSA 87
Dates
31 Aug - 4 Sep 1987.
Place
Zurich (Switzerland).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19084453
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTAINMENT; REACTIVITY; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; RESEARCH PROGRAMS; RISK ASSESSMENT; SOURCE TERMS; SPECIFICATIONS; WATER COOLED REACTORS
Descriptors DEC
ACCIDENTS; COOLING SYSTEMS; REACTOR COMPONENTS; REACTORS; SAFETY

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
CONF-870820--10.